Static and simulated seismic testing of the TRG-7 through -16 shear wall structures
- Los Alamos National Lab., NM (United States)
- New Mexico Univ., Albuquerque, NM (United States)
- Dove (R.C.), Del Norte, CO (United States)
Results from the static, simulated seismic base excitation, and experimental modal analysis tests performed on the TRG-7 through -16 structures are reported. These results were used to establish the scalability of static and dynamic response measured on small structural models to the dynamic response of conventional concrete structures. In addition, these tests provided information concerning cumulative damage effects that occur in concrete structures when they are subjected to different dynamic load sequences. In contrast to previous results obtained in the early part of this program, TRG-7 through -16 responded to simulated seismic excitations with theoretical stiffness values until peak nominal base shear stress levels of 150 psi were reached. A summary of all experimental data obtained during this program is provided. 23 refs., 47 figs., 22 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5355694
- Report Number(s):
- NUREG/CR-5660; LA-11992-MS; ON: TI92000104
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
BUILDINGS
SEISMIC EFFECTS
WALLS
NUCLEAR POWER PLANTS
ACCELEROMETERS
COMPUTERIZED SIMULATION
CONCRETES
CRACKS
DAMPING
DYNAMIC LOADS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
RESPONSE FUNCTIONS
SCALE MODELS
SCALING LAWS
SHEAR
STATIC LOADS
STRAINS
STRESS ANALYSIS
TEST FACILITIES
TRANSDUCERS
BUILDING MATERIALS
FUNCTIONS
MATERIALS
MEASURING INSTRUMENTS
NUCLEAR FACILITIES
POWER PLANTS
SIMULATION
STRUCTURAL MODELS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
360603 - Materials- Properties